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Decontamination of Cells 6 and 7, Building 3019, Following Plutonium- Release Incident

Description: As a result of the evaporation explosion in the Radiochemical Processing Pilot Plant on Nov. 20, 1959, two cells were contaminated with plutonium to a transferable level of 10/sup 8/ d/m/100 sq cm. The area involved measures 40 by 20 by 27 ft high with a total surface area, including equipment, of 10,000 sq ft. The cells were decontaminated by a factor of 1000 in five months by removing loose equipment, debris, and shielding blocks and flushing with 430,600 liters of various decontaminating rea… more
Date: September 11, 1961
Creator: Parrott, J.R.
Partner: UNT Libraries Government Documents Department
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Dissolution of Zirconium Reactor Fuels in Titanium Equipment

Description: Continuous dissolution of Zircaloy-2 in a titanium dissolver appears practical using as a dissolvent refluxing 3 M HNO/sub 2/-l.2 M HF--0.4 M HBF/sub 4/-0.6 M Cr(III)-0.4 M Cr(VI)--0.46 M Zr. Dissolution and corrosion rates were 10 mg/cm/sub 2/-min and 0.0 mil/mo in short term tests, respectively. A stable product solution containing 0.36 M Zr was obtained after addition of aluminum nitrate to complex fluoride ion. Another reagent investigated for use in continuous dissolution was 16 M HNO/sub … more
Date: October 11, 1961
Creator: Gens, T.A.
Partner: UNT Libraries Government Documents Department
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THE PATH OF CARBON IN PHOTOSYNTHESIS

Description: It is almost sixty years since Emil Fischer was describing on a platform such as this one some of the work which led to the basic knowledge of the structure of glucose and its relatives. Today we will be concerned with a description of the experiments which have led to a knowledge of the principal reactions by which those carbohydrate structures are created by photosynthetic organisms from carbon dioxide and water, using the energy of light. The speculations on the way in which carbohydrate was… more
Date: December 11, 1961
Creator: Calvin, Melvin (Nobel Prize lecture)
Partner: UNT Libraries Government Documents Department
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Improved Zirconium Alloys Quarterly Report: January - March 1961

Description: The following report is one of a series of quarterly reports following the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between January 1 to March 31, 1961.
Date: April 11, 1961
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Improved Zirconium Alloys Quarterly Report: April - June 1961

Description: Quarterly report documenting progress on a project to determine an improved zirconium alloy for service in superheated water and steam. This report describes the results of approximately 75 compositions that were prepared prior, and presently are being arc-melted and fabricated into corrosion specimens, continuing the investigations of the effect of zirconium purity and heat treatment on corrosion and resistance.
Date: July 11, 1961
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Hazard Analysis for Cesium Shipments

Description: The rail shipment of large quantities of radiocesium involves a potential accidental release of this material in a readily available form to the biosphere. The magnitude of the associated potential damage to man and his environment is evaluated in this report. The evaluation of the consequences of an accidental release of Cs-137 from the Shielded Transfer Tank, Model II (STT) assumes loss of Cs-137 to the atmosphere or to surface-water. Release to the atmosphere could result from a collision fo… more
Date: May 11, 1961
Creator: Watson, E. C.; Junkins, R. L. & Fuquay, J. J.
Partner: UNT Libraries Government Documents Department
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Production test IP-431-A expansion of overbore test facilities C Reactor

Description: The objective of this production test is to authorize the installation of at least 40 additional large size Zircaloy process tubes in graphite channels that have been enlarged to 2.275 inches at C Reactor and to charge these tubes with large diameter (CVIN) fuel elements to obtain preliminary conversion ratio data and further qualitative data regarding the irradiation behavior of large diameter fuel element designs.
Date: August 11, 1961
Creator: Van Wormer, F. W.
Partner: UNT Libraries Government Documents Department
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Power calculation accuracy with dual downcomer operation

Description: The C reactor is presently, operating with all process water discharging through one downcomer. Pressure measurements at the downcomer lid show the top tray is nearly flooded, thus prohibiting further flow increases until the downcomer is modified or both downcomers are used simultaneously. Operation with two downcomers can result in two sources of error in the power calculation: (1) Errors in measured outlet temperature can occur, apparently due to the increased venting capacity. The magnitude… more
Date: September 11, 1961
Creator: Renberger, D. L.
Partner: UNT Libraries Government Documents Department
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Cesium-137 as an index of the nuclear materials content of coating waste

Description: An experimental program was carried out to evaluate the validity of using the cesium-137 content of coating waste as an indirect measure of the uranium and/or plutonium content. A small number of large volume samples and a large number of normal (small volume) samples of Redox and Purex coating waste were used for the investigations. The distribution of cesium, uranium, and plutonium throughout the two-phase system was determined. a comparison of uranium by direct assay and uranium by cesium-13… more
Date: October 11, 1961
Creator: Schneider, R. A.
Partner: UNT Libraries Government Documents Department
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Process Water Flow Tests, C Reactor

Description: The power calculator at C Reactor and the process pump flowmeters at 190-C use orifice plates as primary sensing elements. These orifices were designed for considerably less flow and at the present higher flows, the reactor riser pressure is appreciably reduced as the result of the inefficiency of the orifices. Only a portion of the differential pressure across an orifice is recovered. The amount is dependent upon the ratio of the orifice diameter to pipe diameter. The permanent loss across the… more
Date: April 11, 1961
Creator: Hamilton, W. D.
Partner: UNT Libraries Government Documents Department
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Flow increase: C reactor

Description: At the request of B-C Maintenance Engineering, this study was initiated to investigate the feasibility of replacing the 190-C and 105-C process water flow-meter orifices with venturi tubes. Specific aspects of the problem studied were potential flow increases, accompanying production increases, costs, and the ability of the existing 190-C pumps and motors to provide the potential flow increase.
Date: May 11, 1961
Creator: Tupper, W. J.
Partner: UNT Libraries Government Documents Department
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Production test IP-376-D, Supplement B Irradiation of MGCR-HDR-3 Test Element

Description: The objective of this supplement to PT-IP-376-D, Irradiation of MGCR-HDR-3 Test Element is to authorize 1000 hours of operation at a maximum test specimen surface temperature of 1700 F. The original production test authorized a test duration of four months at a maximum specimen surface temperature of 1500 F; supplement A authorized extension of the test duration to ten months. The desired increase in surface temperature is requested to demonstrate the general feasibility of operation of the fue… more
Date: July 11, 1961
Creator: Baars, R. E.
Partner: UNT Libraries Government Documents Department
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A study of Columbia River surveillance by closed circuit television

Description: Current Practice -- A patrolman observes river traffic 24 hours a day, seven days a week, from a 50 foot enclosed tower located on the bank of the river. Under normal daylight conditions the opposite shore line and bluffs (2,000`) and approximately three miles both up and down the river can be seen by naked eye with close up identification obtained through use of field glasses. For night time operation a manually operated searchlight is used to sweep the river for moving or floating objects. Pr… more
Date: December 11, 1961
Creator: Maupin, A. A., Jr.
Partner: UNT Libraries Government Documents Department
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Measurement of Dissociation Pressure of Molybdenum Fluoride-Sodium Fluoride Complex

Description: The dynamic (gas saturation) method was used to determine upper and lower limits for the dissociation pressure of the complex formed when MoF/sub 6/ is absorbed by NaF. The limits were 0.4 to 4.6 mm Hg at 100 deg C and 8.4 to 27 mm Hg at 150 deg C. A lower limit, 64 mm Hg, was determined at 200 deg C. As a check on the method the dissociation pressure of the complex UF/sub 6/ - (NaF)/ sub 3/ was determined at 100, 200, and 240 deg C. The measured values were in satisfactory agreement with accep… more
Date: April 11, 1961
Creator: Groves, F. R., Jr.
Partner: UNT Libraries Government Documents Department
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The Homogeneous Decomposition of Hydrogen Peroxide by Plutonium(IV)

Description: The homogeneous decomposition of H/sub 2/O/sub 2/ by HNO/sub 3/, and by HNO/sub 3/ solutions (>1M) containing Pu(IV); Pu(IV) and Pt; Pu(IV) with Cu(II) and Fe(III); and Pu(IV) with Pt, Cu(II), and Fe(III) as a function of temperature is investigated. The range of STAH/sub 2/O/sub 2/! is 10/sup -2/ to 10/sup -1/M, and STAPu(IV)! p 1.25M. The evolution of gas is first order in all cases up to STAHNO/sub 3/! approximately 10M. Above STAHNO/sub 3/! approximately 10M, the reaction is no longer fi… more
Date: September 11, 1961
Creator: Elson, R. E.
Partner: UNT Libraries Government Documents Department
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Fast-Neutron and Gamma Spectrum and Dose in Beryllium Oxide

Description: This report follows a series of tests run to determine the shielding properties of beryllium oxide, conducted at the Battelle Lid-Tank Shielding Facility. Neutron and gamma penetrations through and behind beryllium oxide were measured.
Date: January 11, 1961
Creator: Klingensmith, Raymond W.; Jung, Richard G.; Lindgren, William A.; Epstein, Harold M. & Chastain, Joel W., Jr.
Partner: UNT Libraries Government Documents Department
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Surge suppressors for the PRTR process tube flow meters

Description: Each tube of the PRTR is provided with flow monitoring equipment consisting of a venturi flow meter in the inlet piping, sensing lines containing valves, and a Panellit flow transmitter. The flow transmitter does three things: converts the pressure drop signal of the venturi to a visual readout; provides an electrical signal for recording; and provides a signal to the safety circuit which causes a reactor scram should the flow increase or decrease beyond pre-set valves. After startup of the PRT… more
Date: August 11, 1961
Creator: Hesson, G. M.; Thorne, W. L. & Batch, J. M.
Partner: UNT Libraries Government Documents Department
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PHASE EQUILIBRIA IN MOLTEN SALT BREEDER REACTOR FUELS. I. THE SYSTEM LiF- BeF$sub 2$-UF$sub 4$-ThF$sub 4$

Description: The phase equilibrium relations for the systems limiting the quaternary system LiF--BeF/sub 2/--UF/sub 4/--ThF/sub 4/ are described in detail, along with available information on the quaternary system itself. The implications of the extensive solid solutions in the limiting systems are discussed, and experimental information supporting the conclusions is presented. The optical properties, crystallographic properties, and x-ray diffraction patterns for the phases occurring in these systems are t… more
Date: January 11, 1961
Creator: Weaver, C. F.; Thoma, R. E.; Insley, H. & Friedman, H. A.
Partner: UNT Libraries Government Documents Department
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Power Reactor Program. Progress Report to Savannah River Operations Office, United States Atomic Energy Commission for the Period March 1, 1961 Through March 31, 1961

Description: An evaluation of two thin-walled outer tubes showed that more extensive alpha working of the billet core stock results in more uniform cladding on the extruded tube. In an effort to eliminate breakthrough and to reduce eccentricity, shift, and bending of the mandrel, two experimental coppernickel billets with Zircaloy sleeves were extruded to check a modified billet design. lt was observed that the final grain size of the unalloyed uranium core of a thin- walled outer tube is insensitive to sma… more
Date: May 11, 1961
Creator: Isserow, S.; Anderson, R. W.; Richmond, W. J.; Tuffin, W. B.; Larson, W. L.; Smoot, P. R. et al.
Partner: UNT Libraries Government Documents Department
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Studies of Bismuth Alloys. Liquidus Curves of the Bi-Cu, Bi-Ag, and Bi-Au Systems

Description: The liquidus curves of the Bi-Cu, Bi-Ag, and Bi-Au systems were re- determined by means of a sampling method. The Bi-Ag curve,was somewhat shifted from the previously determined location. The eutectic was found at 262.5 {+-} 0.2{degrees}C at 4.95 {+-} 0.05 atom % silver (2.62 wt %). The Bi-Cu liquidus agreed fairly well with Kleppa's data over the range investigated by him. The discrepancies in the literature in regard to higher copper concentrations were resolved. The.eutectic was determined t… more
Date: August 11, 1961
Creator: Nathans, M. W. & Leider, M.
Partner: UNT Libraries Government Documents Department
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THE DEVELOPMENT OF A DIRECT COUPLED, TRANSISTORIZED, SUB-MILLIMICROAMPERE CURRENT AMPLIFIER

Description: Development of a direct coupled, transistorized current amplifler is reported with sensitivities extending below the millimicroampere region of input currents. The amplifier employs a shunt feedback and exhibits reproducible characteristics. Discovery of this special effect and the design and testing employed in the incorporation of transistors into the amplifier are described. (J.R.D.)
Date: August 11, 1961
Creator: May, F.T.
Partner: UNT Libraries Government Documents Department
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Studies of Bismuth Alloys. II. Distribution of Small Additions of Cu, Ag, OR Au between Solid and Liquid Phases in Bi-Cu, Bi-Ag, and Bi-Au

Description: The distribution of small amounts of radioactive Cu, Ag, and Au between precipitates of these elements and their solutions in bismuth was investigated at different temperatures by sampling the liquid. In all cases the . Doerner-Hoskins law was obeyed. Approximate distribution ratios were calculated and plotted against 1/T. Extrapolation to the melting temperature of the major component X in these Bi-X-Y systems yields values which compare well with the distribution constants obtained either fro… more
Date: August 11, 1961
Creator: Nathans, M. W. & Leider, M.
Partner: UNT Libraries Government Documents Department
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